2012
DOI: 10.1016/j.jnucmat.2011.10.037
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ODS Ferritic/martensitic alloys for Sodium Fast Reactor fuel pin cladding

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Cited by 128 publications
(46 citation statements)
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“…Research works performed during recent years have revealed that ODS (Oxide Dispersion Strengthened) steels are promising materials for fuel pin cladding in Sodium Fast Reactors [1,2]. It appears that the bcc ferritic-martensitic lattice allows for a high resistance to irradiation swelling up to a dose of around 150 displacements per atom (dpa) and nano-oxides significantly improve creep and tensile properties at high temperature (650°C) by blocking the dislocations motion.…”
Section: Introductionmentioning
confidence: 99%
“…Research works performed during recent years have revealed that ODS (Oxide Dispersion Strengthened) steels are promising materials for fuel pin cladding in Sodium Fast Reactors [1,2]. It appears that the bcc ferritic-martensitic lattice allows for a high resistance to irradiation swelling up to a dose of around 150 displacements per atom (dpa) and nano-oxides significantly improve creep and tensile properties at high temperature (650°C) by blocking the dislocations motion.…”
Section: Introductionmentioning
confidence: 99%
“…Oxide dispersion-strengthened (ODS) ferritic steels are being intensely investigated for high-temperature nuclear applications due to their excellent creep properties and swelling resistance [1]. These assets are obtained thanks to a fine-grained body-centred cubic microstructure reinforced by a dense and homogeneous precipitation of yttrium nanooxides.…”
Section: Introductionmentioning
confidence: 99%
“…The generation IV innovative concept of SFR introduces some specifications that are different from those of the past SFR which are not sustained by present materials. Consequently, new materials have to be qualified [1].…”
Section: Introductionmentioning
confidence: 99%